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Futagami, Satoshi; Ando, Masanori; Yamano, Hidemasa
Transactions of the 27th International Conference on Structural Mechanics in Reactor Technology (SMiRT 27) (Internet), 10 Pages, 2024/03
Yamano, Hidemasa; Futagami, Satoshi; Ando, Masanori
Mechanical Engineering Journal (Internet), 10(4), p.23-00043_1 - 23-00043_12, 2023/08
This study has conducted a detailed structural analysis of a reactor vessel (RV) in a loop-type sodium-cooled fast reactor using a general-purpose finite element analysis code, FINAS/STAR, to understand its deformation behavior under extremely high temperature conditions and to identify the areas which should be focused to mitigate impacts of failure. The RV was heated from the normal operation condition to the sodium boiling temperature in the upper sodium plenum during 20 hours assuming depressurization. The analysis has revealed less significant stress and strain which were sufficiently lower than failure criteria. The upper body of RV was identified as the important area in terms of mitigation of structural failure. The RV was eventually deformed downward about 16 cm, resulting in no failure. This effect contributes to maintaining RV sodium level in a long term, thereby enhancing the RV resilience.
Yamano, Hidemasa; Futagami, Satoshi; Ando, Masanori
Proceedings of 29th International Conference on Nuclear Engineering (ICONE 29) (Internet), 7 Pages, 2022/08
This study has conducted a detailed structural analysis of a reactor vessel (RV) in a loop-type sodium-cooled fast reactor using a general-purpose finite element analysis code, FINAS/STAR, to understand its deformation behavior under extremely high temperature conditions and to identify the areas which should be focused to mitigate impacts of failure. The RV was heated from the normal operation condition to the sodium boiling temperature in the upper sodium plenum during 20 hours assuming depressurization. The analysis has revealed less significant stress and strain which were sufficiently lower than failure criteria. The upper body of RV was identified as the important area in terms of mitigation of structural failure. The RV was eventually deformed downward about 16 cm, resulting in no failure. This effect contributes to maintaining RV sodium level in a long term, thereby enhancing the RV resilience.
Futagami, Satoshi; Ando, Masanori; Yamano, Hidemasa
Transactions of the 26th International Conference on Structural Mechanics in Reactor Technology (SMiRT-26) (Internet), 9 Pages, 2022/07
Tsuji, Hirokazu; *; *; Nakajima, Hajime
Journal of Nuclear Science and Technology, 31(4), p.274 - 278, 1994/04
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
Kurihara, Ryoichi; Tachibana, Yukio; Nishihara, Tetsuo; Maruyama, So; Shiozawa, Shusaku; *
Atsuryoku Gijutsu, 32(3), p.154 - 165, 1994/00
no abstracts in English
Tsuji, Hirokazu; *; Nakanishi, Tsuneo*; *; Nakajima, Hajime
JAERI-M 93-209, 64 Pages, 1993/10
no abstracts in English
Tsuji, Hirokazu; *; *; Nakajima, Hajime
JAERI-M 93-144, 69 Pages, 1993/07
no abstracts in English
Tsuji, Hirokazu
Journal of Nuclear Materials, 203, p.187 - 188, 1993/00
Times Cited Count：0 Percentile：0.68(Materials Science, Multidisciplinary)no abstracts in English
; Nakajima, Hajime; Eto, Motokuni
Nucl. Eng. Des., 144, p.305 - 315, 1993/00
Times Cited Count：7 Percentile：60.37(Nuclear Science & Technology)no abstracts in English
; ; *; *; *; Yoshida, Eiichi;
PNC TN9450 91-010, 259 Pages, 1991/10
In order to advancement in materials strength standard on elevated temperature design guide of the FBRs and evaluation method of materials strength behavior, this report are presented about the creep properties of Mod.9Cr-1Mo steels for steam generator, based on the R&D results obtained through the activities of material tests. Contents of the data sheet are as follows; Material : Mod.9Cr-1Mo steels (Base Metal) Plate 7 Heats (F2, F6, F7, F9, F10, NSC1, NSC2) Forging 8 Heats (F4, F5, F8, F11, VIM, ESR, F520, F550) Tube 1 Heats (F3) Test temperature : 450
650
C Test method : According to JIS and FBR Metallic Materials Test Method Test environment : In Air and in Sodium Number of deta : 314 points
; Hirakawa, Yasushi; Furukawa, Tomohiro; *; *; *; *
PNC TN9450 91-004, 71 Pages, 1991/07
In order to advancement in materials strength standard on elevated temperature design guide of the FBRs and evaluation method of materials strength behavior, this report are presented about the low-cycle fatigue properties of Mod.9Cr-1Mo steel, based on the R&D results obtained through the sctivities of material tests. Contents of the data sheet are as follows; [Material ; Mod.9Cr-1Mo steel(SR)] F2 Heat 1,000
1,00012mm
(Plate) F4 Heat 1,0001,000250mm(Forging) F6 Heat 1,0001,00025mm(Plate) [Environment; In Air and in Sodium] [Test temperature ; 450, 500, 550, 600 and 650C] [Strain rate ; 0.1%/sec (10
mm/mm/sec)] [Strain range ; 0.38% 1.86%] [Number of deta ; 83 points]
; Hada, Kazuhiko; Koikegami, Hajime*; *
Nihon Genshiryoku Gakkai-Shi, 33(5), p.475 - 481, 1991/05
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
Hada, Kazuhiko; Motoki, Yasuo; Baba, Osamu
JAERI-M 90-148, 231 Pages, 1990/09
no abstracts in English
; Kaji, Yoshiyuki; ; Nakajima, Hajime; Baba, Osamu
Juel-Conf-71, p.243 - 274, 1989/04
no abstracts in English
Nucl.Eng.Des., 97, p.279 - 296, 1986/00
Times Cited Count：2 Percentile：32.46(Nuclear Science & Technology)no abstracts in English
; *; ; Sanokawa, Konomo; *; *
Nihon Genshiryoku Gakkai-Shi, 26(4), p.70 - 79, 1984/00
no abstracts in English
Hada, Kazuhiko
JAERI-M 8709, 99 Pages, 1980/02
no abstracts in English
; ; ; ; ; *; *; *; *; *
Nihon Genshiryoku Gakkai-Shi, 21(3), p.245 - 267, 1979/00
Times Cited Count：3no abstracts in English
Kondo, Tatsuo;
Kikai Sekkei, 19(9), p.31 - 38, 1975/09
no abstracts in English
